氦预辐照降低钨毛生长的温度阈值

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-09-10 DOI:10.1016/j.jnucmat.2025.156134

Quan Shi , Shin Kajita , Noriyasu Ohno

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引用次数: 0

摘要

在利用线性等离子体装置的研究中，氦等离子体辐照在钨上形成模糊纳米结构已经被广泛报道，结果表明这种结构只有在超过900 K的温度下才会形成。在这项研究中，在两步实验中，绒毛在~ 750 K下生长：1。氦等离子体在900 K以上温度下辐照衬底；2. 在~ 750 K的温度下继续辐照。结果发现，在预辐照后的~ 750 K处，绒毛继续生长，其生长速率甚至高于高温时的生长速率，在厚度达到~ 1800 nm时，绒毛生长达到饱和。利用热解吸光谱分析探讨了可能的机理。

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Reduction of the temperature threshold for tungsten fuzz growth by helium pre-irradiation

The formation of fuzzy nanostructures on tungsten by helium plasma irradiation has been widely reported in studies utilizing linear plasma devices, with results indicating that such structures only develop at temperatures exceeding 900 K. In this study, fuzz grows at ∼750 K in a two-step experiment: 1. substrate irradiated by helium plasma at a temperature over 900 K; 2. continue the irradiation at a temperature of ∼750 K. It is found that fuzz continues growing at ∼750 K after the pre-irradiation with a growth rate even higher than that at high temperatures, and the growth saturates after reaching a thickness ∼1800 nm. The possible mechanism is discussed using thermal desorption spectroscopy analysis.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.